EPJ Nuclear Sci. Technol.
Volume 2, 2016
|Number of page(s)||11|
|Published online||15 January 2016|
A study of different cases of VVER reactor core flooding in a large break loss of coolant accident
OKB GIDROPRESS, 21, Ordzhonikidze Street, Podolsk, Moscow Region, 142103, Russian Federation
* e-mail: firstname.lastname@example.org
Received in final form: 3 August 2015
Accepted: 21 October 2015
Published online: 15 January 2016
The paper covers the results of VVER core reflooding studies in fuel assembly (FA) mockup of 126 fuel rod simulators with axial power peaking. The experiments were performed for two types of flooding. The first type is top flooding of the empty (steamed) FA mockup. The second type is bottom flooding of the FA mockup with level of boiling water. The test parameters are as follows: the range of the supplied power to the bundle is from 40 to 320 kW, the cooling water flow rate is from 0.04 to 1.1 kg/s, the maximum temperature of the fuel rod simulator is 800 °C and the linear heat flux is from 0.1 to 1.0 kW/m. The test results were used for computer code validation.
© Y.A. Bezrukov et al., published by EDP Sciences, 2016
This is an Open Access article distributed under the terms of the Creative Commons Attribution License (http://creativecommons.org/licenses/by/4.0), which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
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